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Scientific Basis for Storage Criteria for Interim Dry Storage of Aluminum-clad Fuels

Published online by Cambridge University Press:  15 February 2011

R. L. Sindelar ,
H. B. Peacock ,
P. S. Lam Jr. ,
N. C. Iyer ,
M. R. Louthan Jr.  and
J. R. Murphy
R. L. Sindelar
Affiliation:
Westinghouse Savannah River Company, Aiken, SC 29802
H. B. Peacock
Affiliation:
Westinghouse Savannah River Company, Aiken, SC 29802
P. S. Lam Jr.
Affiliation:
Westinghouse Savannah River Company, Aiken, SC 29802
N. C. Iyer
Affiliation:
Westinghouse Savannah River Company, Aiken, SC 29802
M. R. Louthan Jr.
Affiliation:
Westinghouse Savannah River Company, Aiken, SC 29802
J. R. Murphy
Affiliation:
Westinghouse Savannah River Company, Aiken, SC 29802
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Abstract

An engineered system for dry storage of aluminum-clad foreign and domestic research reactor spent fuel owned by the United States Department of Energy is being considered to store the fuel up to a nominal period of 40 years prior to ultimate disposition. Scientifically-based criteria for environmental limits to drying and storing the fuels for this system are being developed to avoid excessive degradation in sealed and non-sealed (open to air) dry storage systems. These limits are based on consideration of degradation modes that can cause loss of net section of the cladding, embrittlement of the cladding, distortion of the fuel, or release of fuel and fission products from the fuel/clad system. Potential degradation mechanisms include corrosion mechanisms from exposure to air and/or sources of humidity, hydrogen blistering of the aluminum cladding, distortion of the fuel due to creep, and interdiffusion of the fuel and fission products with the cladding.

The aluminum-clad research reactor fuels are predominantly highly-enriched aluminumuranium alloy fuel which is clad with aluminum alloys similar to 1100, 5052, and 6061 aluminum. In the absence of corrodant species, degradation due to creep and diffusion mechanisms limit the maximum fuel storage temperature to 200°C. The results of laboratoryscale corrosion tests indicate that this fuel could be stored under air up to 200°C at low relative humidity levels (< 20%) to limit corrosion of the cladding and fuel (exposed to the storage environment through assumed pre-existing pits in the cladding). Excessive degradation of fuels with uranium metal up to 200°C can be avoided if the fuel is sufficiently dried and contained in a sealed system; open storage can be achieved if the temperature is controlled to avoid excessive corrosion even in dry air.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 412: Symposium V – Scientific Basis for Nuclear Waste Management XIX , 1995 , 99
Copyright
Copyright © Materials Research Society 1996

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References

1. Abbott, David G., Bringhurst, Allan R., and Denzel, Dr. Fillmore, L., in DOE Spent Nuclear Fuel Challenges & Initiatives, p. 10, American Nuclear Society, ANS Order No. 700214, La Grange Park, IL, 1994.Google Scholar
2. Gilbert, E. R., Bailey, W. J., Johnson, A. B. Jr., and McKinnon, M. A., Nuclear Technology Vol.89, February 1990, pp. 141–161.Google Scholar
3. Schneider, K. J., Mitchell, S. J., and Johnson, A. B. Jr., in High-Level Radioactive Waste Management. Proceedings of the Third International Conference, American Nuclear Society, La Grange Park, IL, 1992, pp. 1159–1165.Google Scholar
4. Sindelar, R. L., Peacock, H. B. Jr., Iyer, N. C., and Louthan, M. R. Jr., in High-Level Radioactive Waste Management. Proceedines of the Sixth International Conference,American Nuclear Society, La Grange Park, IL, 1995, p. 647.Google Scholar
5. Sindelar, R. L., Caskey, G. R., Peacock, H. B. Jr., and Lam, P. S., in High-Level Radioactive Waste Management. Proceedings of the Sixth International Conference, American Nuclear Society, La Grange Park, IL, 1995.Google Scholar
6. DOE/SNF/PP001, Rev. 1, Draft June 30, 1995, U. S. Department of Energy, Environmental Management, Office of Spent Fuel Management and Special Projects.Google Scholar
7. Peacock, H. B. Jr., Sindelar, R. L., and Lam, P. S., in proceedings of the 18th International Meeting on Reduced Enrichment for Research and Test Reactors, September 18–21, 1995, Paris, France.Google Scholar
8. Snelgrove, J. L., Hoffman, G. L., Frontroth, R. L., McDonell, W. R., Peacock, H. B., Whitacre, R. F., and Copeland, G. L., ANL/NPR-90/008, Argonne National Laboratory, March 1990.Google Scholar
9. Hoffman, G. L., Sugondo, S., and Neimark, L. A., results to be presented at the DOE Spent Nuclear Fuel & Fissile Material Management Conference, Embedded Topical Meeting, Reno Nevada, June 1996.Google Scholar
10. Burke, S. D. and Howell, J. P., in DOE Spent Nuclear Fuel Challenges & Initiatives, p. 118, American Nuclear Society, ANS Order No. 700214, La Grange Park, IL, 1994.Google Scholar
11. Johnson, A. B. Jr., ”Bases for Extrapolating Materials Durability in Fuel Storage Pools,” in DOE Spent Nuclear Fuel Challenges & Initiatives, p. 83, American Nuclear Society, ANS Order No. 700214, La Grange Park, IL, 1994.Google Scholar
12. Louthan, M. R., Jr. and Iyer, N. C., in DOE Spent Nuclear Fuel Challenges & Initiatives, p. 333, American Nuclear Society, ANS Order No. 700214, La Grange Park, IL, 1994.Google Scholar
13. Godard, H. P., Jepsom, W. B., Bothwell, M. R., and Kane, R. L., The Corrosion of Light Metals, John Wiley & Sons, Inc., 1967.Google Scholar
14. Alwitt, R. S., The Aluminum-Water System, Chapter 3 in Oxides and Oxide Films, Vol.4, pp. 169–254, ed. by Diggle, J. W., Marcel Dekker, New York, 1976.Google Scholar
15. Field, D. J., Oxidation of Aluminum and Its Alloys, Chapter 19, Aluminum Alloys - Contemporary Research and Applications, ed. by Vasudevan, A. K. and Doherty, R. D., Vol. 31 Treatise on Materials Science and Technology, Academic Press, Inc. Boston, MA, 1989 Google Scholar
16. Hunter, M. S. and Fowle, P., J. Electrochemical Society, Vol. 103 (9), 482–485, 1956.Google Scholar
17. Peacock, H. B., Jr., Sindelar, R. L., Lam, P. S., and Murphy, T. H., Westinghouse Savannah River Company report, WSRC-TR-95-0345, November 1995.Google Scholar
18. Bradford, S. A., in Metals Handbook, Volume 13, Corrosion, Ninth Edition, ASM International, 1987.Google Scholar
19. Vernon, W. H. J., Trans. Farad. Soc., Vol.27, 1931, p. 255.Google Scholar
20. Graedel, T. E., J. Electrochemical Society, Vol. 136 (4) p. 204C, April 1989.Google Scholar
21. Aziz, P. M. and Godard, H. P., Journal of Industrial and Engineering Chemistry, 44 (8), August 1952.Google Scholar
22. Maiya, P. S. and Kassner, T. F., Argonne National Laboratory, ANL/ACTV-91–6, (1991).Google Scholar
23. Ritchie, A. G., Journal of Nuclear Materials, Vol.102, 170–182, 1981.Google Scholar
24. Bennett, M. J., Myatt, B. L., Silvester, D. R. V., and Antill, J. E., J. Nuclear Materials, Vol. 57, pp. 221–236, 1975.Google Scholar
25. Bennett, M. J. and Price, J. B., Journal of Nuclear Materials, Vol.101, 44–55, 1981.Google Scholar
26. McGillivray, G. W., Green, D. A., and Greenwood, R. C., Journal of Nuclear Materials, 208 (1994) pp. 81–97.Google Scholar
27. Louthan, M. R., Jr. and Derrick, R. G., Met. Trans., 6A, 1655–1657, 1975.Google Scholar
28. Blackburn, P. E. and Gulbransen, E. A., Jnl Electrochemical Society, Vol.107 (12), 944–950, 1960.Google Scholar
29. Draley, J. E. and Ruther, W. E., Jnl. Electrochemical Society, Vol.104 (6), 329–333, 1957.Google Scholar
30. Leidheiser, H. Jr., and Das, N., Jnl. Electrochemical Society, Vol.122 (5), 640–641, 1975.Google Scholar
31. Alani, R. and Swann, P. R., British Corrosion Journal, Vol.12 (2), pp. 80–85, 1977.Google Scholar
32. Miller, R. F. and Sindelar, R. L., Westinghouse Savannah River Company report WSRC-TR-95-0121, April 1995.Google Scholar
33. Caskey, G. R., Jr., Westinghouse Savannah River Company report WSRC-TR-93-502, September 1993.Google Scholar
34. Farrell, K. and King, R. T., Met. Trans., Vol.4, 1223–1231, 1973.Google Scholar
35. Solbrig, C. W., Krsul, J. R., and Olsen, D. N., in DOE Spent Nuclear Fuel Challenges & Initiatives, p. 89, American Nuclear Society, ANS Order No. 700214, La Grange Park, IL, 1994.Google Scholar